Volume 3B: Design and Analysis 2018
DOI: 10.1115/pvp2018-84280
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Experimental Results and Numerical Analyses of Tests Conducted on Large Alloy 600 Centre Cracked Tensile Specimens

Abstract: Some components of the main primary circuit of PWR nuclear power plants contain nickel-base alloy 600 parts (steam generator (SG) tubes, steam generator partition plates, lower internal radial supports). It is well known that this alloy is prone to stress corrosion cracking in the primary water environment. In 2002, surface cracks were discovered for the first time in SG partition plates of EDF 900 MWe NPP. The integrity of the SG containing these cracks must be demonstrated for all operating conditions, inclu… Show more

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“…The assessment of cracked structures is still an active field of research in mechanical engineering. [1][2][3][4] Charts 5 can be used to estimate some quantities of interest on cracked structures but they are not accurate enough and are focused on specific cases. Finite element (FE) methods can be used to improve results and to deal with arbitrary crack configurations.…”
Section: Introductionmentioning
confidence: 99%
“…The assessment of cracked structures is still an active field of research in mechanical engineering. [1][2][3][4] Charts 5 can be used to estimate some quantities of interest on cracked structures but they are not accurate enough and are focused on specific cases. Finite element (FE) methods can be used to improve results and to deal with arbitrary crack configurations.…”
Section: Introductionmentioning
confidence: 99%